ML18039A343

Rev 1 to COLR Cycle 8 for Browns Ferry Nuclear Plant Unit 3.

ML18039A343
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Site:	Browns Ferry
Issue date:	04/17/1998
From:	Bruce A, Keys T, Riley E TENNESSEE VALLEY AUTHORITY
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ML18039A341	List: ML18039A340 ML18039A343
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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 CORE OPERATING LIMITS REPORT (COLR), REVISION 1 FOR CYCLE 8 OPERATION (SEE ATTACHED) 98052i0107 9805ii PDR noaCK 0500mve P PDR

TVA a~lUclear FUel TVA COLR-BF3C8 Core Operating'Lir Report Revision i, Page i J33 980417 806 QA RE't:ORD Browns Ferry Nuclear Plant Unit 3, Cycle 8 CORE OPERATING LIMITS REPORT (COLR)

TENNESSEE VALLEYAUTHOMTY Nuclear Fuel Division BWR Fuel Engineering Department

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By: 'repared Date:

Earl E. Riley, Engineer' Specialist BWR Fuel Engineering Verified By:

Alan L.,Bruce, Nuclear Engineer Date: tt ta tt'u I IL W N CC z

I'L ~r5o BWR Fuel Engineering Approved By: Dat" '//7 Cl Ih u'

'T. A. Keys, M ger la eo BWR Fuel Engineering Reviewed By: Date: 4 ~7 ~E eactor Engineering Supervisor Jt Reviewed ~g/g PORC Cha Revision 1,(4/17/98) Mid-cycle 8 Outage Fuel Loading Modifications Pages Affected: 1-3,6,15-18

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.@ore Operating Limit ort Revision 1, Page 2 Revision I og Revision Date D~eecri cion Affected P.a es 0 2/6/97 Initial Release 1 4/17/98 Revise references and add MAPLHGR 1-3, 6, 15, Data to accommodate fuel loading modifications during the mid-cycle 8 16-18 (re-outage number only)

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TVANuclear Fuel TVA-COLR-BF3CS i:om Operating L'imttort Revision l, Page 3..

INTRODUCTION This Core Operating Limits Report for Browns Ferry Unit 3, Cycle 8 is prepared in accordancet with the requirements of Browns Ferry Technical Specification 6.9.1'.7.

The core operating limits presented here were developed using NRC-approved methods (References 1 and 2). Results from the reload, analyses for Browns Ferry Unit 3, Cycle 8 are documented:in Reference 3 and'6.

The following:core operating limits.are'included in. this report:

a. Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specification 3.5.I)'.

Linear Heat Generation Rate (LHGR) Limit (Technical'pecification 3.5.J)

c. Minimum Critical Power Ratio Operating Limit (OLMCPR)

(Technical Specification 3.5.'K/4.5.K) a

d. Average Power Range Monitor (APRM) Flow Biased Rod Block Trip Setting (Technical Specification 2.1.A.l.c, Table 3;2.C, and Specificati'on 3.5.L)

e. Rod Block Monitor (RBM) Upscale (Flow Bias) Tr'ip Setting and Clipped Value (Technical Specification Table 3.2.C)

2. APLHGR.LIMIT(TECHNICALSPECIFICATION 3.5.I)

The APLHGR limit for each type of fuel as a function of exposure is shown in Tables 1-9. The APLHGR limits for the GE11 assemblies are. for the most limiting lattice at each exposure point. The specific values. for each lattice are given in References 4 and i5

4k Qi TVANuclear Fuel TVA-COLR-BF3CS Core Operating Limi ort Revision l, Page 4

3. LHGR LIMIT(TECHNICALSPECIFICATION 3.5.J)

The LHGR limit for unit 3 cycle 8 is fuel type dependent, as shown below:

~Fuel T. e LHGR Limit PSXSR/GE7B 13.4 kw/ft GE11 -

1'4.4 kw/ft

4. OLMCPR (TECHNICALSPECIFICATION 3.5.K/4.5.K)

a. The OLMCPR is equal to the fuel type and exposure dependent MCPR limit at rated flow and rated power shown in:Figures 1-2 multiplied by the Kfshown in Figure,3, where; Z = 0.0 or whichever is greater.

Zi = 0.90 sec (Specification 3.3.C.1 scram time limit to 20%

insertion from fully withdrawn )

i Zi = 0.710 + 1.65

.N 2 (0.053) n n

g i=i Zi Save n

where; n = Number of surveillance.rod tests performed to date in cycle (including BOC test).

Zi = Scram time to 20% insertion from fully withdrawn of the i th rod.

N = Total number of active rods measured in Specification 4.3.C. 1 at BOC.'.

For the performance of Surveillance Requirement 4.5.K;2.a (prior to initial scram time measurements for the cycle),

'7 =1.0

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c. For the performance of Surveillance Requirement 4.5.K.2.b, '6 shall be determined in accordance with 4.a above.

.5. APRM FLOW BIASED ROD BLOCK TRIP SETTING (TECHNICAL SPECIFICATION 2.1.A.1.c, TABLE 3.2.C, AND SPECIFICATION 3.5.L).

The APRM-Rod Block trip setting shall be:

SRB g (0 58W + 57%)

where:

SRB = Rod Block setting in percent of rated thermal power (3293 MWt)

W = Loop recirculation flow rate in percent of rated Note: Under certain conditions, the APRM Rod Block setting must be adjusted'by FRP/CMFLPD. See Technical Specification 3;5;L.

6. RBM UPSCALE'(FLOW BIAS) TRIP SETTING AND CLIPPED VALUE (TECHNICALSPECIFICATION TABLE 3.2.C)

The RBM Upscale trip setting shall be:

< (0.66W+ 460')

where:

Trip.level setting is'in percent of rated thermal power (3293 MWt)

W = Loop recirculation flow rate in percent of rated RBM upscale flow-biased setpoint,clipped at 112 percent. rated reactor power.

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TVA Nuclear Fuel TVA-COLR-BHCS Core Operating Limi ort Revision l, Page 6

7. REFERENCES

1. NEDE-24011-P-A-13, "General Electric Standard Application for Reactor Fuel",

August 1996.

2. NEDE-24011-P-A-13'-US, "General'Electric Standard Application for Reactor Fuel (Supplement for United States)"., August 1996:

3. J11-02967SRL'R Rev. 0, "Supplemental Reload Licensing Report for Browns Ferry Nuclear Plant Unit 3 Reload 7 Cycle 8",.January 1997.

4. J11-02967MAPL Rev. 0, "Lattice-Dependent MAPLHGR Report for Browns Ferry Nuclear Plant Unit 3 Reload 7'Cycle 8", January 1997; 5: 24A5178AA Rev. 1, "Lattice-Dependent.MAPLHGR,Report for Browns Ferry Nuclear Plant Unit 3 Reload'6 Cycle 7", August 1995.

"6. GE letter'LB8262-98-042, "Browns Ferry Nuclear Plant Unit 3 Cycle 8 Safety Evaluation of Mid-Cycle Modified. Core Loading on SRLR Applicability - GE Proprietary Information", dated April 16, 1998.

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TVANuclear Fuel TVA-COLR-BF3CS Core Operating Limi ort Revision 1, Page 7 Table 1 APLHGR Limits for Bundle Type GE11-P9HUB323-5G5.0/4G4.0 (GE11)

Most Limiting Lattice for Each Exposure Point Average Planar. Exposure APLHGR Limit

~GWD/ST kw/ft 0.0 10.41 0.2. 10.44 1.0 10.54 2.0 10.75 3.0 11.01 4.0 11.30 5.0'.0 11;62 11'.95 7.0 12.21 8.0 12.42 9.0 12.64 10.0 12.82 12.5 12;70 15.0 12.38 17.5 12.06 20.0 11.73 25.0 10.97 30.0 10.25 35.0 9.57 40.0 8.93 45.0 8.24 50;0 7.49 55.0 6.55 57.7 6.08

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TVANuclear, Fuel'ore TVA-COLR-BF3C8 Operating Limi ort Revision l, Page 8 Table 2 APLHGR Limits for Bundle Type GE11-P9HUB323-8G4.0 (GE11)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.0 10.81 0.2 10.83 1'.0 10.91 2.0 11.11 3.0 11.36 4;0 11'.63 5.0 11.93 6.0 12.25 7.0 12.38 8.0 12.5 1:

9.0 12.65 10;0 12.79 12.5 12.71 15.0 12.39 17.5 12.07 20.0 11.72 25:0 10.97 30.0 10.25 35.0 9:57 40.0 8.93 45.0 8.25 50;0 7.51 55.0 6.58 57.72 6.10

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TVANuclear Fuel TVA-COLR-BF3CS Core Operating. Limi ort Revision I, Page 9 Table 3 APLHGR Limits for Bundle Type GE11-P9HUB325-14GZ (GE11)

Most Limiting Lattice for Each Exposure Point Average Planar Exposure Limit

~GWD/ST kw/ft 0.0 9.48 0.2 9.57 1.0 9.79 2.0 10.08 3.0'.0 10.38 10.71 5.'0 11.06 6.0 11.44 7.0 11.80 8.0 12.07 9.0 57.27'PLHGR 10.0 12.5 15.0 12.23'2.37-12.36 12.13 17.5 11.90 20.0 11.59 25.0 10.87 30.0 10.18 35.0 9.52 40.0 8.88 45.0 '8.24 50.0 7.60 55.0 6.81 6.41

.ii TVANuclear Fuel TVA-COLR-BF3CS Core Operating Limit ort Revision 1, Page 10 Table 4 APLHGR Limits for Bundle Type P8DRB283 (LTA)

(P8X8R)

Average Planar-Exposure APLHGR Limit

~GWD/ST kw/ft 0.2 1'1.2 1.0 11.2 5.0 11.7 10.0 12.0 15.0 12.0 20.0 11.9 25.0 11.3 30.0 10.8 35.0 10.4 40.0 10.0 45.0 9.5

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J TVA Nuclear Fuel TVA-COLR-BF3CS Core Operating Limi ort Revision I, Page l 1 Table 5 APLHGR Limits for Bundle Type PSDRB314 (LTA)

(P8XSR)

Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.2 10.6 1.0 10.7 5.0 11.3 10.0 11.7 15.0 11.5 20.0 11.2 25.0 10.6 30.0 10.1 35.0 9.7 40.0 9.3 45.0 8.8

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'Core Operating Limi ort Revision 1, Page 12 Table 6 APLHGR Limits for. Bundle Type P8DRB299 (P8X8R)

Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.0 10.71 0.2 10.'75 1.0'.0 10.86 11.01 3.0 11.19 4;0 11.35 5.0 11'.47 6.0 11;62 7;0 11.78 8'.0 11.95 9.0 12.09 10.0 12.20 12.5 12.37 15.0 12.47 20.0 12;37 25.0 11.77 35.0 '0.65 42.13 9.36

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TVANuclear Fuel TVA-COLR-BF3CS

'Core Operating Limit ort Revision 1, Page 13 Table 7 APLHGR Limits for Bundle Type BP8DRB284L (GE7B or BPSX8R)

.Average Planar Exposure APLHGR Limit

~GWD/ST . kw/ft 0.2 11.2 1.0 11.3 5.0 11.8 10.0 12.0 15.0 12.0 20.0 11.9 25.0 11.3 30.0 10.8 35.0 10.1 40;0 9.4 45.0 8.8

TVANuclear, Fuel TVA-COLR-BF3CS

'Core Operating Limit ort Revision'1, Page 14 Table 3 APLHGR Limits for Bundle Type PSDRB284Z (P8X8R)

Average Planar Exposure APLHGR Limit

~GWD/ST kw/ft 0.2 11.2 1.0 11.2 5.0 11.7 10.0 12.0 15.0 12.0 20.0 1'1.9 25.0 11.3 30.0 10.8 35.0 10.4 40.0 9.9 45.0 9.5

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'Core Operating Limi ort Revision 1, Page 15'able 9

APLHGR Limits for Bundle Type P8DRB265L (P8X8R)

Average Planar Exposure APLHGR Limit

.~GWD/ST kw/ft 0.2 11.6 1.0 11.6 5.0 12.1 10.0 12.1 15;0 12.1 20.0'5.0 11.9'1.3 30.0, 10.7 35.0 10.2 40.0 9.6

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TVANuclear Fuel TVA-COLR-BF3CS

'Core Operating Limit ort Revision 1, Page 16 FlgUI'l 1 MCPR Operating Limit for PSXSR X GE7B (BPSXSR)

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L I I I I ~"

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I I I I I I to EOC8

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0.0 0.1 0.2 0.8 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Option B Option A E~R BOC8 to EOC8 0 tion A Tau=1.0 1.33

• 0 tion B Tan=0.0 1.30

• Use this value at BOC8 prior to performing scram time testing.

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! TVANuclear Fuel TVA'-COLR-BF3CS

'Core Operating Limi ort Revision 1, Page 17 Flgllre 2 MCPR Operating Limit for GE11

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1.29 I

1.28 0.0 0.1 0.2 0.3 0.4 0.5 0.8 0.7 0.8 0.9 1.0 Option B Option A H~R BOC8 to EOC8 0 tion A Tau=1.0 1.35

• 0 tionB 1.32 Tan=0.0

~ Use this value at BOC8 prior to performing scram-time testing.

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TVANuclear Fuel TVA-COLR-BF3C8

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Core Operating Limi~ort Revision I, Page 18 (Final)

Figure 3 GEXL-Plus Kf Curve OLMCPR Flow Corrections 1.4 117.0%

1.3 112.0%

107.0%

102.5%

1 e2 1.0 20 30 40 50 60 70 80 90 100 Total, Core Flow (% rated):

For 40%< WT,< 100%, Kf = MAX,[ 1.0, A-0.00441*WT,]

WT< 40%, Kf = [A - 0.00441+WT] + [1.0+0.0032+(40-WT)]

WT' 100%. 'Kf = 1;0 where: WT = PercentofRated CoreFlow, and A = .constant wluch depends on the Flow Control Mode and the Scoop

'Tube Setpoint as noted below.

Flow Control Mode Scop Tube Set 1oint, A MANUAL. 102:5 % 1.3308 107.0 % 1.3528 MANUAL'ANUAL'ANUAL 112;0 % 1.3793 117.0 % 1.4035 AUTOMATIC N/A 1.4410 Note: Flow Corrections are given for P8x8R and'BP8x8R bundles. These corrections are conservative when compared to GE11 flow corrections which do not have the additional correction'factor of

[1.0+ 0.0032*(40-WT)] below'40% flow.

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